| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1740585 | Progress in Nuclear Energy | 2014 | 9 Pages |
•A code for analysis of steam generator developed based on CUPID.•The code supports unstructured meshes to fit complex geometry of steam generators.•The code can predict subcooled boiling with its wall heat partitioning model.•The predictions show good agreement with the FRIGG experiment data.
CUPID-SG (CUPID code for Steam Generators) is a computer code for analyzing two-phase flows and heat transfer in PWR steam generators. It was derived from CUPID (Component Unstructured Program for Interfacial Dynamics), which is a component-scale thermo-hydraulic analysis code developed at KAERI (Korea Atomic Energy Research Institute). CUPID-SG shares the code structure with CUPID, which adopts two-fluid, three-field conservation equations, and semi-implicit numerical algorithms. CUPID-SG supports unstructured meshes to handle complex geometries, and adopts constitutive models of two-fluid model based system analysis codes for two-phase boiling flows. FRIGG tests are the benchmark in confirming the correct implementation of the transport models and the applicability of CUPID-SG to two-phase flows over heated tube bundles. A comparison with the FRIGG experiments showed that the constitutive models are properly implemented, and that CUPID-SG is capable of analyzing vertical two-phase boiling flows over tube bundles typically appearing in steam generators.
